ML20039B456

LER 81-011/03L-0:on 811113,containment Isolation Valves Opened & Ventilation Process Initiated W/Containment Air Monitor RM-050/051 Inoperable.Caused by Personnel Error. Valves Closed

ML20039B456
Person / Time
Site:	Fort Calhoun
Issue date:	12/11/1981
From:	Bare M OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20039B453	List: ML20039B452 ML20039B456
References
LER-81-011-03L, LER-81-11-3L, NUDOCS 8112230058
Download: ML20039B456 (4)

Text

PC FORM* 353 U.S. NUCLEAR REGULATORY COMMISSION e n1 LICENSEE EVENT REPORT cONTseteLccel l_  ! l l l

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10 12 18 1568l@l69 11 11 OCCxET NuttaER 1 l 3181 l l@l 112 EVENT DATE 74 75 l ll 11811Sol@

REPORT D ATE EVENT OESCRIPriCd AND PROSAaic. ;3NSEQUENCES h

-TO 121 IDuring cold shutdown following refueling, the containment air monitor, RM-050/051, was i taken out of service to perform the Type C leak rate test on its containment isolation

.t a l a i [ valves (PCV-742E/F/G/H) for 60 psig integrity. The purge penetrations (PCV-742A/8/C/D)I were also closed. An air sample was taken by the Health Physics group which indicated Io i4 Ithat the containment atmosphere was below unrestricted M.P.C. The air flow from con- l tainment was classified ,s ventilation only and not a gaseous waste-release, therefore ll o i s i l Tech. Spec. 2.9.3.(IV) did not apply. The containment isolation valves were opened I and ventilating process initiated; however, a footnote (4) in Table 2-1 in Tech. Spec.

i a is 1 ISection 2.14 requires containment ventilation valves to be closed if RM-050/051 are in-1 operable with respect to containment. The oncoming operating shift secured the con-l o 17 l Itainment purge until RM-050/051 could be returned to service. RM-060/061/062 monitorect the stack gases during this time interval with no abnormal indications.

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7- S 9 10 11 '? 13 18 19_ 20 SEQUENTIAL OCCURRENCE REPORT REVISION ggq pg EVENTVEAR REPORT NO CODE TYPE NO.

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33 33 36 40 el 42 43 CAUSE DESCalPTION AND CORRECTIVE ACTIONS h ji ! O l l Calculations were performed to ensure that the release _ did not violate limits as l

.ii i, j l_ described in the Technical Specifications. Personnel were re-instructed. Changes __J

,, ,, j ; to 'the Tech. Specs. are being considered. _

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/ 8 9 80 ST 'h PCWER OTHER STATUS 15 O RY DISCOVERY DESCRIPTION y lH j@ l 0l 0 l 0l@l N/A l lAl@l OPERATOR OBSERVATION l ACTIVITY CO TENT OF RELEASE AMO'1NT OF ACTIVITY LOCATION OF RELE ASE 6 [Z_j PELEASE@D LZj@l N/A l l N/A l i 9 9 to 11 44 46 80 PEntCNNEL F XPOGURES l 5 j.7 l l0YU l0 l@l Zl@l l PE ASONNEL INJunlEi l3pll0YU"l"0l@f"3 l N ') 11 12 80 LOES OF OR DA%fAGE TO FACILITY h TvPE Of SCP'P TION  %,/

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-. OnrAJivvao - 402-426.4011- R

LER 81-011

' Omaha Public Power District Fort Calhoun . Station Unit No. -1 ,

Docket No. 05000285 ATTACHMENT N0. 1 Safety Analysis In.an extended outage _such as the Fort _Calhoun Station Cycle 7 core reload,- the containment is often .in an unrestricted vent mode. The Health Physics Technicians take~ daily containment' air samples and RM--

050/051 monitors the containment atmosphere. In addition, radiation monitor RM-060/061/062. monitor gases' released up the plant ventilation stack. If any one of the five mentioned process radiation monitors

. exceeds its predetermined high alarm setpoint, a ventilation isolation actuation signal (VIAS) is sent from the Engineered Safeguards Features (E.S.F.) to'the containment ventilation isolation valves, terminating the venting operation.

With RM-050/051 not monitoring containment air, opening PCV-742A/

B/C/D violates Technical Specification 2.14 (Table 2-1). - Howeve'r, RM-060/061/062 still monitor the gases removed from the -containment and

-these radiation monitors would have terminated the vent upon receipt of a high radiation signal.

During the period of the violation, the airborne activity of the air released from containment was less than the maximum permissible L activity allowed for an unrestricted area. This air was further diluted with air from the auxiliary building before being released up the stack.

At no' time during th,is event did tne three remaining process . radiation monitors show abnormal readings.

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LER 81-011 Omaha Public Power District Fort Calhoun Station Unit No.1 Docket No. 05000285 ATTACHNEM' N0. 2 Corrective Action The event has been reviewed with the personnel involved. An Operations Memorandum was issued to ensure the proper action will be taken in the future.

A review of Technical Specification 2.14 is being undertaken to consider possible changes / clarification.

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LER 81-011 Omaha Public Power District Fort Calhoun Station Unit No.1 Docket No. 05000285 ATTACHMENT NO. 3 Failure Data This is the first event involving venting the c niainment with less than M.P.C. with RM-050/051 out of service.

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